ML20078F489

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Rev 0 to Ei Hatch Nuclear Plant Unit 1 Cycle 16 Colr
ML20078F489
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 10/31/1994
From:
GEORGIA POWER CO.
To:
Shared Package
ML20078F444 List:
References
NUDOCS 9411150282
Download: ML20078F489 (18)


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GEORGIA ' POWER COMPANY '

EDWIN I. HATCH NUCLEAR PLANT UNIT 1 FUEL CYCLE 16 CORE OPERATING LIMITS REPORT REVISION 0 5

Southern Nuclear Operating Company .

Post Office Box 1295 Binningham, Alabama 35201 '

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9411150282 941107 PDR ADOCK 05000321 - -

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GEORGIA POWER COMPANY EDWIN I. IIATCII NUCLEAR PLANT UNIT 1 FUEL CYCLE 16 CORE OPERATING LIMITS REPORT REVISION 0 G

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Southern Nuclear Operating Company ,

Post Office Box 1295 Birmingham, Alabama 35201 i

9*1111'[10282 9 #+1 1 0 /

PDk ADDEF ( >LO Ou 3 21 P POR

interoffice Correspondence Georgia Power d DATE: October 25,1994 RE: Hatch Project Support - Licensing Core Operating Limits Report for Hatch 1 Cycle 16 Revision 0 File: Fuel Cycle Technical Img: HL-4726 FROM: S. J. Bethay ,  :/;

TO: ALL UNIT 1 TECHNICALISPECIFICATIONS MANUAL HOLDERS By amendment 168 to the Unit 1 Technical Specifications, the NRC authorized relocation of certain fuel-related limits from the Technical Specifications to the adjunct Core Operating Limits Report (COLR). This letter transmits to all Unit 1 Technical Specifications manual holders a copy of Revision 0 of the COLR for Hatch 1 Cycle 16. This document should be utilized in conjunction with the Unit 1 Technical Specifications, as referred to in the Specifications. Normally, the shift tecimical advisor or reactor engineer will use this report.

Where necessary, the fuel limits from the COLR are included in plant procedures.

Please discard Revision 1 of the COLR for Hatch 1 Cycle 15, which was issued in May 1993, since it is no longer applicable. If you have questions regarding Revision 0 of the Unit 1 COLR for Cycle 16, please contact me at extension 8-821-7392 or telephone number (205) 877-7392.

SRP/sp colrwp Enclosure cc: NORMS

1 l

EDWIN 1. HATCH NUCLEAR PLANT UNIT 1 FUEL CYCLE 16 CORE OPERATING LIMITS REPORT l

1 TABLE OF CONTENTS Section Title Page 1.0 Introduction 1 2.0 Limiting Control Rod Pattern 1 ,

3.0 APLHGR Limits 2 4.0 MCPR Operating Limits 11 4.1 Two Recirculation Loop Operation 11 4.2 Single Recirculation Loop Operation 11 5.0 LHGR Limits 15 6.0 References 15 Revision 0 i October 1994

. .1 TABLE OF CONTENTS (Continued) j l

LIST OF FIGURES l Figure No. Title Pace 3-1 MAPFAC y 3 3-2 MAPFAC p 4 3-3 APLHGR Limits Versus Average Planar Exposure (BP8DRB284H) 5 3-4 APLHGR Limits Versus Average Planar Exposure (GE9B-P8DWB330-10GZ-80M-150-T) 6 3-5 APLHGR Limits Versus Average Planar Exposure (GE9B-P8DWB315-8G4.0-80M-150-T) 7 3-6 APLHGR Limits Versus Average Planar Exposure (GE9B-P8DWB314-8G4.0-80M-150-T) 8 3-7 APLHGR Limits Versus Average Planar Exposure (GE9B-P8DWB331-10GZ-80M-150-T) 9 3-8 APLHGR Limits Versus Average Planar Exposure (GE13-LUA - GE13-P9HTB327-12GZ-100M-146-T-RECON) 10 4-1 Power-Dependent MCPR Multiplier (Kp) 12 4-2 Flow-Dependent MCPR Limits (MCPR p) 13 4-3 MCPR Limit as Function of Average Scram Time and Fuel Type 14 Revision 0 ii Octo'oer 1994

EDWIN L HATCH NUCLEAR PLANT UNIT 1 FUEL CYCLE 16 CORE OPER ATING LIMITS REPORT

1.0 INTRODUCTION

The Core Operating Limits Report (COLR) for Plant Hatch Unit 1 Cycle 16 is prepared in accordance with the requirements of Technical Specification 6.9.1.11. The core operating limits presented herein were developed using NRC-approved methods (References 1 and 2), Results from the reload analyses for the General Electric (GE) fuel in Unit 1 Cycle 16 are documented in References 3 and 4.

The following cycle-specific core operating limits are included in this report:

a. Operation with a Limiting Control Rod Pattern (for a Rod .

Withdrawal Error (RWE)) - Technical Specification 3.3.F.  :

b. Average Planar Linear Heat Generation Rate (APLHGR) -

Technical Specification 3.11.A.

c. Minimum Critical Power Ratio (MCPR) - Technical Specifications 3.11.C and 4.11.C.
d. Linear Heat Generation Rate (LHGR) - Technical Specification 3.11.B.

2.0 LIMITING CONTROL ROD PATTERN (Technical Specification 3.3.F)

Both Rod Block Monitor (RBM) channels shall be operable as specified in Technical Specification 3.3.Fand when: i

a. THERMAL POWER is < 90% of RATED THERMAL POWER and the MCPR is < 1.70 or
b. THERMAL POWER is .>_90% of RATED THERMAL POWER and the MCPR is < 1.40.

Revision 0 1 October 1994

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report 3.0 APLHGR LIMITS (Technical Specification 3.11.A) l The APLHGR limits are given by the applicable rated-power, rated-flow limit l taken from Figures 3-3 through 3-8, multiplied by the smaller of either: )

a. The factor given by Figure 3-1 or
b. The factor given by Figure 3-2.

For the fuel types whose APLHGR limits are shown in Figures 3-3 through 3-8, the APLHGR limit shall be applied to each axial location in the fuel assembly.

As required by GESTAR Amendment 19, the hand-calculated APLHGR values for a multi-lattice (i.e.,GE9-330, GE9-331, and GE13-LUA) fuel must be less than or equal to the APLHGR limits shown in Figures 3-4,3-7, and 3-8, respectively. When APLHGR values are determined by the process computer, the lattice-dependent APLHGR limits are used. Under these conditions, some axial locations may have APLHGR values exceeding the values shown in Figures 3-4,3-7, and 3-8.

4 1 Revision 0 2 October 1994 !

Plant IIatch Unit 1 Fuel Cycle 16 Core Operating Limits Report i 1 l ./ }

l I

-- 102.5%

- 107 %

" ~

112 % '.

"* ~ ~ ~ ~~ ~ ~

i h e.no -

I

?

/ . *.i. l MAPLHGR e a MAPFAC,* MAPLHGRsm E

MAPLHGRsm = STANDARD MAPLHGR LIMITS B l I P< e.7o MAPFACe = MINIMUM [MFRPD,, MAPMULT,)

1 g  !

MAPMULT = 1.0 FOR FLOW > 61% '

8- /

j = 0.86 FOR FLOW 5 61%

v  !

5 MFRPO,(F) = MINIMUM [ 1.0, A, + B,F)

D N ' l

' F= FRACTION OF RATED CORE FLOW.

l MAXIMUM l l l CORE FLOW (

(% RATED) A, B, '

8M ~-

102.5 0 4861 0.6784 107 0 0 4574 06758 l l' 112.0 0.4214 0.6807 l 117.0 0.3828 0.6886 I

l l  !

l t I

$ 40 w 4e 9 60 l n se n m (VRE FLOW (% rated)

FIGURE 3-1  ;

MAPFACr  ;

Revision 0 3 October 1994

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report 1.0 E

O k

k2 0.9 - g,OT

$ ogs#*

< 0.8 -- $O SINGLE LOOP OPERATION (SLO)

MAPLHGR,= MAPFAce' MAPLHGRsm MAPLHGRam = STANDARD MAPLHGR LIMITS d 0.7 --

FOR 25% > P: NO THERMAL LIMITS MONITORING REQUIRED h (SLO.TLO) NO LIMITS SPECIFIED

\ FOR 25% s P < 30%:

(SLO, TLO) f MAPFAC, = 0.585 + 0.005224 (P - 30%)

o 0.6 - FOR i 50% CORE FLOW g

f <

LU 1 ,

MAPFAC,=0.433 + 0.005224 (P - 30%) l W FOR > $0% CORE FLOW i o l 0: 0.5 - N FOR 30% s P:

Lu N (SLO, TLO) g i N MAPFAC,=1.0 + 0.005224 (P - 100%)

Q.,

  • 50% CORE FLOW FOR 52% s P; (SLO) MAPFAC,= 0.75 0.4 ---

l l l l l l l l l f 20 25 30 40 50 60 70 80 90 100 l

POWER (% rated) l l

FIGURE 3-2 MAPFAC, Revision 0 4 October 1994 )

Plant IIatch Unit 1 Fuel Cycle 16 l Core Operating Limits Report l 1

l l

14-

.UNACCERTABLEI s 33 :OPEkATIONj -

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,+ -

$ - ' l 2.4 12.4

~ 12 h h 33)

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a+ r; ;

cf. :6 >

h LOW EXPOSURE COORDINATES Q: '

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7jg.

0 ',' '

X Y

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b 0.0 10.8 -

0**

% 10 - 0.2 10.s ACCEPTABLE 2.0 11.2 "

4.0 11.5 OPERATION L -

6.0 11.8 f 8.0 12.1 9 r 10.0 12.3 l c

12.5 12.4 FUEL BP8DRB284H l TYPE

80 - MIL CHANNELS 8.5 l l l 1 8 '

O 5 10 15 20 25 30 35 40 45 AVERAGE PLANAR F.XPOSURE (GWd/st)

FIGURE 3-3 APLHGR LIMITS VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: BP8DRB284H) l Revision 0 5 October 1994  !

1

i L .

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report

.I' , :l: -lL .. ll ' -L ' t i 1312 . . . ,U'ACCEPTABi5)

N e 12 -

! 12A8 Q. OPERATION 3 ..

l I ^

11.72

, " ,T '

g LOW EXPOSURE i

- ' ~ 1l .I Wk .d5;

_ COORDINATES , _ ,,

" X Y T-O -

10 0.0 11.52 10.1 Q' EM  %-

t- 0.2 11.58 i ,c 5,

12 '",;

3.0 12.10 V 8.79 7 u,n .

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3 4.0 12.30 i g8 5. 12.52 ACCEPTABLE 6.0 12.71 7-7.0 8.0 12.88 13.05 OPERATION a 9.0 13.19 \ .

10.0 13.30 6 12.5 13.36 FUEL TYPE: '

GE98-P8DWB330-10GZ 80M 150-T 5.70 at $1.64 l l

  • 5-0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/st)

$$$S!NSYUN O CF E PLANAR EAPOSURE FIGURE 3-4 APLHGR LIMITS VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB330-10GZ-80M-150-T)

Revision 0 6 October 1994

1 Plant Hatch Unit 1 Fuel Cycle 16 <

Core Operating Limits Report l

13 f 4 .'l : <

ins: UNACCERTdBLE1.

12.4 ,% OPERATION;

~

11. 'i' ~

LOW EXPOSURE

~

w COORDINATES g

y e 10 0.0 11.85

,4u h I$ U2$$ '

3 9; 2.0 12.17 %T

$ 3.0 12.35 8.96'

  • I i

4.0 12.56 'j' a 5.0 12.75 6.0 12.96 ACCEPTABLE ,

7.0 13.15 7 8.0 OPERATION 13.24 9.0 13.31 h ^

10.0 13.41 4 6 12.5 13.50 1 FUEL TYPE: GE98-P80WB315-8G4.0-80M 150-T 5.86--

l l { GWd/st 5

0 5 10 15 20' 25 30 35 4 4 M AVERAGE PLANAR EXPOSURE (GWd/st)

FIGURE 3-5 APLHGR LIMITS VERSUS AVERAGE PLANAR EXPOSURE (Fuel 'lype: GE9B-P8DWB315-8G4.0-80M-150-T)

Revision 0 7 October 1994

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report gg i 1m i. 2, 13.16 .UNACCNPTABLE 4 -

12 q .

.OPERATIONJ

~-

I 11.80 LOW EXPOSURE C -

g c""o'=*5 x y  ;. .,'

10- 0.0 11.83 N '+ '

4 -

t- 0.2 11.90 3 1.0 12.01 r

9' 2.0 12.17 " '

o 3.0 12.34 8.98 5 4.0 12.54 ,

%8 5.0 12.74 ACCEPTABLE 6.0 12.94 l

\ >

7.0 13.12

--4 OPERATION \

7 8.0 13.22 '

9.0 13.30 l 10.0 13.40 -

F'JEL TYPE: _

6 12.5 13.50 l GE98-P8DWB3144G4.0-80M 150-T at $1.87 l l GWd/st 20 25 30 35 40 45 50 0 5 10 15 '

AVERAGE PLANAR EXPOSURE (GWd/st) i i

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i FIGURE 3-6 APLHGR LIMITS VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB314-8G4.0-80M-150-T)

Revision 0 8 October 1994 l

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report

~

qc- 1 .; -: p-12.98 . UNACCEPTABLE:

12 -- J 12.1 e OPERATidNJo 1 .

a; ii;! '

LOW EXPOSURE k" [

\

COORDINATES .. .g; ._. . ,

k OS 9:qk ..;;h ;; ,

b 0.2 11.62 9.77) '"^a 4 s:p -

E 1.0 11,75 r,' 7' 3 g 2.0 11.95 E 3.0 12.17 o" <

~

3 4.0 12.41 AF - <

ga 5.0 12.ss ACCEPTABLE " F 6.0 12.90 7.0 13.07 OPERATION 7 8.0 13.22 9.0 13.32 .

10.0 13.25 i 6 12.5 13.13 FUEL TYPE: LB "-

GE9B-P8DWB331 10GZ-80M-150-T l at 50.06 q D i

l GWd/st 5

0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWdist)

APLHGR UMIT FOR MOST UMmNG LATTICE AS FUNCTION OF AVERAGE PLANAR EXPOSURE FIGURE 3-7 APLHGR LIMITS .

VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB331-10GZ-80M-150-T)

Revision 0 9 October 1994 I

1

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report

}. ;l.

,3

4. -

UNACCERTABLE; ,

12 ___ _ _ _ . _11.70 _ ' OPERATION; M

11 q / fCOORDINATES UEEE_

COW EXPOSURE ' 'l 1 j *[

,V-g x y 10.86 h 0.0 11.07 10.19 -

b' '

Q '

e 9 3.0 11.70 O 4.0 11.70 8.90, ,

5 5.0 11.70 x <. - ',

%8 sj jjj0 , ACCEPTABLE ,

8.0 11.70 7 e -

9.0 11.70 OPERATION "

7 10.0 11.70 t gg 12.5 11.70 I J 6.51 AT 6 F3L TYPE: GE13LUA 57.27 GMT G E13-P 9 HTB 327 12GZ-100M-146-T-REC ON 5 ~

0 5 10 15 20 25 30 35 ~40 '45 50 55 AVERAGE PLANAR EXPOSURE (GWd/st)

NOTE:

APLHGR LIMIT FOR MOST LIMITING l LATTICE AS FUNCTION OF AVERAGE l PLANAR EXPOSURE i i

i l

FIGURE 3-8 APLHGR LIMITS VERSUS AVERAGE PLANAR EXPOSURE (GE13-LUA -- GE13-P9HTB327-12GZ-100M-146-T-RECON)

Revision 0 10 October 1994

i Plent Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report 4.0 MCPR OPERATING LIMITS (Technical Specifications 3.11.Cand 4.11.C)

The MCPR operating limit (OLMCPR) is a function of fuel design, average enm time, core flow, number of operating recirculation loops, operability of c:M of-cycle recirculation pump trip (EOC-RPT) system, and core power. Note th:.i in Fipr 4-3, the rated-power and rated-flow OLMCPR is fuel-type dependent; e ;?..the Option B limits are 1.29 for GE7 and GE9 fuels, and 1.41 for GE13 fuel. The values shown in Figure 4-3 apply to all combinations of operating strategies for all exposures when the EOC-RPT systern is operable.

4.1 Two Recirculation Loon Operation For 25% .<_ power < 30%, the OLMCPR is given in Figure 4-1. For power _> 30%, the OLMCPR is the greater of either:

a. The applicable limit determined from Figure 4-2 or
b. The appropdate K,given in Figure 4-1, multiplied by the appropriate limit shown in Figure 4-3 where the scram time dependenc: is given in Technical Specification 4.11.C.2.

4,2 Single Recirculation Iron Operation For single-loop operation, the OLMCPR shall be 0.01 greater than the two-loop value which is determined as specified in Section 4.1.

Revision 0 11 October 1994

Plant IIatch Unit 1 Fuel Cycle 16 Core Operating Limits Report 2.6- '

> 50% FLOW 7 2.5 i/ OPERATING LIM!T MCPR(P) = Kp

  • OPERATING LIMIT MCPR(100)

FOR P < 25%: NO THERMAL LIMITS MONITORING REQUIRED 2.4 l NO LIMITS SPECIFIED g i FOR 25% $ P < Peem.(WHERE P.. = 30% FOR HNP - 1,2 Kp = (K.. + 0.02(30% - P))/OLMCPR(100) 8 2.3 i AND l

  1. 2*2 ~T~ K.*= 2.00 FOR < 50% CORE FLOW

~

Km.= 2.40 FOR > 50% CORE FLOW

@b v

a u. 2*1 50% F y/LOW 7 FOR 30% $ P < 45%:

Kp = 1.28 + 0.0134 (45% P) vi g l FOR 45%5 P < 60%:

gx 2.0 Kp = 1.15 + 0.00867 (60% P) m q %, FOR 60% < P:

" {g1.5b -

Kp = 1.0 + 0.00375 (100% P)

O"

u. l 1.4 e$

i l

I

$a$ 1.3 ,

1.2 h

< l i

E I*I I N's I p, ,, l 1.0 20 25 30 40 50 60 10 80 90 100 POWER (% RATf;D)

FIGURE 4-1 POWER-DEPENDENT MCPR MULTIPLIER (K,)

Revision 0 12 October 1994

Pl nt lirtch Unit 1 Fuel Cycle 16 Core Operating Limits Report 1.7 -

MAXIMUM FLOW RATE =

FOR Wc (% RATED CORE FLOW)2 40%

117 % j MCPR(F)= MAX (1.20, AfWc/100+Bf) l f 112 % i 1.6

--f-j// 107% l MAX FLOW Af Bf I

/ //! 102.5 %

l 117.0 112.0

-0.632

-0.602 1.809 1.747 1.5 - -

107.0 -0.586 1.697 102.5 -0.571 g

7/l 1.655 g 1 / r 1.4 - -- l-I '

1.3 -

I i

I

, i EUR We (% RATED CORE FLOW) < 40%

MCPR(F)=(AfWc/100+Bf)

  • [1+0.0032(40-Wc)]

1.1 -

30 40 50 60 70 80 90 100 110 120 CORE FLOW (% rated) i FIGURE 4-2 FLOW-DEPENDENT MCPR LIMITS (MCPRr)

Revision 0 13 October 1994

Plant Httch Unit 1 Fuct Cycle 16 Core Operating Limits Report j l

1.42 l l l l  ! l l l l I

1.40 GE13 LUA 1.38 h 1.36 e

1.34 n:

1.32 - - - - - - - - _

o. l GE9B __

h 1.30 l I GE7B l

< 1.28 5

a g 1.26 lii 1.24 ,

1.22 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 TAU Note: MCPR limits are applicable to all exposures less than end-of-cycle minus 2000 MWD /st when the EOC-RPT system is inoperable, and applicable to all exposures when the EOC-RPT system is operable.

FIGURE 4-3 MCPR LIMITS AS FUNCTIONOF AVERAGESCRAM TIME ANDFUEL TYPE Revision 0 14 October 1994

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~

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report i

5.0 LHGR LIMITS (Technical Specification 3.11.B)

The LHGR limit is 13.4 kW/ft for all GE7 fuel. The LHGR limit for GE9 and GE13 fuels is 14.4 kW/ft. ,

o

6.0 REFERENCES

1. " General Electric Standard Application for Reactor Fuel,"

NEDE-240ll-P-A-10-US . March 1991.

2. Letter, L. P. Crocker (MRC) to W. G. Hairston (GPC), " Issuance of Amendment No.168 to Facility Operating License DPR-57 and Amendment 106 to Facility Operating License NPF Edwin I. Hatch Nuclear Plant, ,

Units 1 and 2 (TACS 73614/73615)," December 29,1989.

3. " Supplemental Reload Licensing Submittal for Edwin I. Hatch Nuclear Plant Unit 1 Reload 15, Cycle 16," General Electric Document 24A5156, Revision l 0, September 1994.
4. "Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis," NEDC-31376-P. December 1986.
5. Edwin I. Hatch Nuclear Plant Unit 1 Technical Specifications . Bases 3.3.F and 3.11.A,B, and C.

I l

I l

Revision 0 15 October 1994

- _ . _ . _ , .